ML19351D751
| ML19351D751 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/13/1976 |
| From: | French J YANKEE ATOMIC ELECTRIC CO. |
| To: | Purple R Office of Nuclear Reactor Regulation |
| References | |
| WYR-76-19, NUDOCS 8011170910 | |
| Download: ML19351D751 (7) | |
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YANKEE ATOMIC ELECTRIC COMPANY 20 Turnpike Road Westborough, Massochusetts 01581
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February 13, 1976 D
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United States Nuclear Regulatory Commission Ib Washington, D. C.
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@! e Attention: Office of Nuclear Reactor Regulation s ]$,
Mr. Robert A. Purple, Chief Operating Reactors Branch #1
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Reference:
1.
License No. DPR-3 (Docket No. 50-29) ps 2.
USNRC Letter dated December 11, 1975 k
Dear Sirs b
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T In reply to your letter, Reference 2, requesting informat -
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I ther evaluate the plant inservice program and water chemistry control of the steam generators we have prepared the attached response.
We trust this meets your needs.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY V1 J.
French Msnager of Operations REMR/kg Enclosures 1490 80111're g
C Regu nory Docket B]g Response to USNRC Letter of December 11, 19 M S $,f,a, @ %, %
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Request 1.
Provide the results of all steam generator tube inspections prior to conversion from a phosphate treatment to all volatile treatment (AVT), and the results of all steam generator tube inspections during AVT operation.
This should include:
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a.
Approximate date of inspection and reason for inspection
Response
Five hydro leak test inspections were performed prior to November 1970 for the purpose of identification of leaking tubes. The approximate dates are as follows:
March, 1967 Steam Generators 3 and 4 July, 1967 Steam Generators 1 and 2-November, 1968 Changed to AVT Chemistry August, 1969 Steam Generators 1 and 4 March, 1970 Steam Generators 1
August, 1970 Steam Generators 1 and 3 Since August 1970, eddy current, examinations of five steam generators have been performed to. determine the relative wall condition of des-ignated tubes. Additionally, hydro leak tests were performed to identify any actual lenkers.
November,' 1970 Steam Generator 4
November, 1971 Steam Generator 1.
June, is74 steam benerator 4
November, 1975 Steam Generator 1 and 4 Request 1.b. Number of tubes inspe'eted in each steam generator and' identification of each tube inspected by row and column.
Response
During the November 1970 inspection, 75 tubes in steam generator No. 1 were examined by means of eddy current techniques. Twenty were randomly selected and no data was recorded; data was recorded for 55 tubes, approximately 3% of the tubes in the steam generator.
During the November 1971 inspection data from the examination of 98 tubes (6%) in steam generator No I was recorded.
During the June 1974 inspection data from the examination of 87 tubes (5%) in steam generator No. 4 was recorded.
During the November 1975 inspection data from the examination of 150 tubes (9%) in steam generator No. 1 and 157 tubes (9%)
in steam generator No. 4 was recorded.
The identification of each tube inspected by row and column is listed in 1.c. below.
Request 1.c. List of all tubes with eddy current indications by percent loss of wall thickness.
Response
The eddy current indications of the above inspections are listed below:
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N:vember(,"1970 inpacetien of cteam g:nzrat r No. 4 Tubes having less than 50% indication:
123.-133, K23, K27, K30 Tubes having an indication of approximately 50%:
B36, S46, E18, E28, F23, Ji9, K29, K32, K33, K35, M33 Tubes having an indication of more than 50%:
G31, J24, J31
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Tubes having an indication of 100%
J23, K31, L31, Tubes having no indication of defects:
A31", B41, B51, B56, B61, E23, 719, F26, F27, F31, F36, G27, G.35,129,131, J18, J27, J28, K26, K36, M29, M31, N19, N23, 018, 023, 027, 028, P26, P31, P36, U31, Z31 November, 1971 inspection of steam generator No. 1:
Tubes having approximately 25% indication:
G21, J22,'L27, 031 Tubes having less than 50% indication:
J23, K41, K47, L23, M25, M26, 029, P24, P29 Tube.s having an indication of approximately 50%:
J24, L31, L41, M28, Q29 Tubes having an indication of more than 50%:
J42, J46, K44, M31, M46, N24, P25, P31, Q31 Tubes having an indication of 75% and 100%, respective 1Iy:
L30 and J45 Tubes having no indication of defects:
H21, H22,120-I23,141-I49, J40, J41, J44, J47, J48, K22, K24, K25, K40, K42, K43, K45, K48, L22, L24, L25, L26, L28, L29,. L44-48, L40, M23, M24, M27, M29, M30, M40-M45, N25-N28, N31, 024-027, 030 P26, P30, Q24-Q28, Q30.
June, 1974 inspection of steam generator No. 4:
Tubes having indications of defects:
G24 % 56%
K26 % 56%
H24 % 75%
K27 < 20%
H25 N 75%
K32 < 20%
122 % 30%
L27 % 40%
I27 < 20%
L28 < 20%
K23 % 30%
L29 < 20%
K24 % 80%
L32 4 75%
K25 100%
i Tubes having no indication of defects:
F22-F33, G22, G23, G25-G30, G32, G33, H22, H23, H26-H32, 123-I26, I28-I33, J25-J30, J32, J33, K12, K22, K29, K30, K33, L22-L24 5
L30, L33, M22-M32, N32, N33 g
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November,1975 in:pictica cf ctean g2n2rstWr No.1:
Tubes having percentage indication of defects:
G31 58%
K36 100%
H27 59%
J38 42%
J24 39%
M42 73%
K33
'8%
M25 35%
Tubes having no indications of defects:
F 27, 28, 29, 30, 31, 32, 33, 34, 35, 36, 37, 38, 39, 40, 4!
42 Row G, Column 26, 27, 28, 29, 30, 32, 33, 34, 35, 36, 37, 38, 39, 40, 4 s
42 H,
15, 21, 26, 28, 30, 31, 32, 34, 36, 38, 39, 40, 41, 42 1,
24, 25, 26, 27, 28, 30, 31, 32, 34, 36, 38, 39, 40, 41, 49 J,
21, 27, 28, 29, 30, 31,'32, 33, 35, 36, 39, 40, 41 K,
18, 24, 27, 28, 29, 30, 31, 32, 35, 37, 38, 39, 40, 41, 4 L,
21,24,25,26,27,31,32,33,34,35,36,37,38,39,43 41 M.
23, 24, 26, 27, 28, 29, 30, 36, 37, 38, 39, 40, 41' N,
18, 21, 25, 26, 31, 35, 36, 37, 38, 39, 40 1
0, 24, 27, 28, 29, 30. 31, 32, 33, 34, 35, 36, 37, 38-The November 1975 inpsection of steam gen'erator No. 4:
Tubes having percentage indication of defects:
F.3':
52%
J27
'20%
"32 45%
LOO 37%
H37 72%
J29
<20%
K35 37%
N30 31%
122
<20%
J35
<20%
L23 38%
N31 30%
I27
<20%
K23 38%
L28 32%
N33 65%
"J20 67%
K27
<20%
L29 28%
035 43%
J26 34%
K29
<20%
L37.
50%
Tubes hav.ing no indications of defects:
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Row F, Column 21-34, 36-39 G,
21-23, 25-30, 32-39 H,
20-23, 26-32, 35, 36, 38, 39 I,
20, 21, 23-26, 28-39 J,
21, 25, 28, 30, 32, 33, 34, 36-39 K,
20, 21, 22, 34, 36-39 L,
20, 21, 22, 24, Su, JJ-36, 39 M,
20-25, 27-32, 34-39 N,
20-29, 32, 34-39 Request 1.d. Identification of all tubes plugged and the. tube plugging limit used.
Response
The following tubes were plugged as a result of leaks found during hydro leak tests:
March, 1967, Steam Generator 3: G29, G36, H25 H27, H30, H34, 135, J34, L31 July, 1967, Steam Generator 1: L42 Steam Generator 2:
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August, 1969, Secam Gensrster 13 J37,.
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H33(J22, L26 j, ]O
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March 1970,.
G18, L43, P27 August, 1970, Steam Generator 1:
J43, K23, K46, N29 N30, 042 Steam Generator 2:
N25, J35 The following tubes exceeded the plugging limit of 50% or were obvious leakers and were plugged:
November, 1970, Steam Generator 4: G31, J23, J31, K31, L25, L31, M33 November, 1971, Steam Generator 1: J42, J43, J45, J46, L30 M31, N24, P25, P31 June, 1974 Steam Generator 4: G24, H24. H25, K24, K25, K26, L27*, L32 November, 1975, Steam Generator 1: G31, H27, J38*, K33, K36, M42 Steam Generator 4: 434, H37, J20, K32*, L37, N33, 035*
- Between 40% and 50% indication Request 2.
Describe the secondary water chemistry for six months prior
- to termination of phosphate treatment and from the onset of transition to AVT to the present.. This should include:
a.
Normal specifications for steady state limits (including range of Na/PO ratio for phosphate treatment.
4
Response
Prior to the conversion from phosphate treatment to AVT in November, 1968 steam generator chemistry was kept within the following general guidelines:
Phosphate N
5 ppm Chloride 0.1 ppm pH 9.7 - 10.0 Chemistry control consisted of the following:
a.
Continuous hydrazine feed of 1-5 ppb adjusted to maintain residual ammonia in the condensate to <0.5 ppm.
b.
Continuous morpholine feed to maintain % pH 9 in the stene condensate - feed system. Phosphate feed to the steam generators consisting of 4 parts trisadium phosphate and 1 part disodium phosphate sufficient to maintain pH and phosphate levels in the steam generators.
c.
Intermittent blowdown of about 0.005% of total daily steam flow.
d.
Phosphate analyses on steam generator blowdown water were done routinely. No sodium analyses or sodium / phosphate ratios were performed.
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TrcasIkat'Limito.-
Reque-t Respon se :--
There were no specified chemistry limits 'for' transiebts Howeve'r,.
steam gene.rator chemistry was followed during and.following'the transient ' operating 'pe'riods.. Extensive blowdown was utilized for :
the control of total solid and phosphate concentrations that resulted from the transient condition.
On several occasions, analysis indicated the presence of free hydroxide. The possible consequences of the phosphate caused free hydroxide anomoly
. prompted.the discontinuance of the phosphate treatment and the initiation of the total volatile (AVT) chemistry.
Request 2.c.
Description of procedures implemented for transition from phosphate to AVT (indicating any sludge lancing performed and quantity of material removed).
Response
No formal written procedures were, developed for tiic conversion to AVT. Phosphate treatment was simply stopped and the chemistry allowed to change over several months.
No sludge lancing was performed.
Request 2.d.
A graph or plot of the secondary water chemistry showing the following as a function of time for each steam generator:
(1) Phosphate concentration; (2)
Sodium concentratica; (3) pH; (4) Conductivity in umho/cm, applicable only for AVT; (5) Hydroxide concentration, applicable'only for AVT; (6) Weight of phosphate-removed, applicable only for AVT.
Response
Considering the years of operation of the plant under phosphate treatment and under AVT secondary water chemistry can be best summarized as follows:
Phesphate Chemistry All Volatile Treatment To Nov., 1968 Since Nov., 1968 Phosphate 2-5 ppm pH
'9.7-10.0 8'.5 - 9.1 Conductivity 30-50 u mhos 3-5 u mhos Chlorine
<0.1 ppm
<0.1 ppm Silica.
<0.5 ppm
<0.5 ppm inte'mittent -
Intermittent'to 1975 Blowdown r
0.005% total Continuous 1975 -
Steam Flow 0.1% of total steam Hydroxide
'Not Routinely Not Routinely Analyzed.
Analyzed Comparison of ammonia, pH and conductivity data used to evaluate presence or absence of free hydroxidG t.
~NRC,onu 195 uC. NUCLEAR REGULATLRY cnMMISSloN DOCKET NUMBE R n 70s
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50-29 8
..NRC OlSTRIBUTION roR PART 50 DOCKET MATERI AL TO:
NRC FROM: Yankee Atomic Elec. Co.
DATE OF DOCUMENT Westborough, Mass. 01581 2<13-76 J.L. French DATE RECEIVED 2-17-76 CLETTER ONOTOnt2ED PROP BNPUT F ORM NUMDER oF COPIES RECEsVED 266 ORIGIN AL OI UNC L ASSIFIE D O COPY 40 ocsCRiPrioN Ltr re our 12-11-75 ltr...trans the ENCLOSURE Response to USNRC Letter of Dec. Il c following:
1975 re plant inservice inspection progra
,& water chemistry control of the steam generators......
(40 cys enc'1 rec'd) bbNMQ i
h PLANT NAME:
Yankee Rowe L
SAFETY FOR ACTION /INFORMATION ENVIRO DHL 2-18-76 ASSIGNED AD :
ASSIGNED AD :
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PROJECT MANAGER:
BURGER PROJECT MANAGER :
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